ML20210C778
| ML20210C778 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 09/08/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210C781 | List: |
| References | |
| NUDOCS 8609180426 | |
| Download: ML20210C778 (15) | |
Text
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UNITED STATES p
g NUCLEAR REGULATORY COMMISSION D
j WASHINGTON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOMINION ELECTRIC COOPERATIVE DOCKET NO. 50-338 NORTH ANNA POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 85 license No. NPF-4 1.
The Nuclear Regulatory Comission (the Comissioni has found that:
A.
The application for amendment by Virginia Electric and Power Company, et al., (the licensee) dated January 3,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (il that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (iii that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8609180426 860908 PDR ADOCK 05000330 P
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2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. NPF-4 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.85, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
$\\
Lester S. Ru enstein, Director PWR Profect Directorate #2 Division of PWR Licensing-A
Attachment:
Changes'to the Technical Specifications D' ate of Issuance:. September 8,1986
i ATTACHMENT TO LICENSE AMENDMENT NO. 85 TO FACILITY OPERATING LICENSE NO. NPF-4 DOCKET NO. 50-338 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contai, vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Page 3/4 1-6 3/4 1-6a B3/4 1-2 i
l
REACTIVITY CONTROL SYSTEMS BORON DILUTION VALVE POSITION LIMITING CONDITION FOR OPERATION 3.1.1.3.2 The following valves shall be locked, sealed or otherwise l
secured in the closed position except during planned boron dilution or makeup activities a.
1-CH-217 or b.
1-CH-220, 1-CH-241, FCV-1114B and FCV-11138.
APPLICABILITY.: MODES 3, 4, 5, and 6 ACTION:
With the above valves not locked, sealed or othervise secured in the l
closed position:
a.
In MODES 3 and 4 be in COLD SHUTDOWN within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> b.
In MODES 5 and 6 suspend all operations involving positive reactivity changes or CORE ALTERATIONS and lock, seal or otherwise secure the valves in the closed position within 15 minutes.
SURVEILLANCE REQUIREMENTS 4.1.1.3.2 The above listed valves shall be verified to be locked, sealed or otherwise secured in the closed position within 15 minutes after a planned boron dilution or makeup activity.
NORTH ANNA-UNIT 1 3/4 1-5 Amendment No. 3
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
For the all rods withdrawn, beginning of core life condition a.
< 0.6 x 10-4 ak/k/'F below 70 percent RATED THERMAL POWER
< 0.0 x 10-4 ak/k/'F at or above 70 percent RATED THERMAL POWER Less negative than -4.4 x 10-4 ak/k/'F for the all rods l
b.
withdrawn, end of core life at RATED THERMAL POWER.
Specification 3.1.1.4.a - MODES 1 and 2* only#
APPLICABILITY:
Specification 3.1.1.4.b - MODES 1, 2 and 3 only#
ACTION:
With the MTC more positive than the limit of 3.1.1.4.a above:
a.
i 1.
Establish and maintain control rod withdrawal limits sufficient to restore the MTC to within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
2.
Maintain the control rods within the withdrawal limits established above until subsequent measurement verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
i 3.
Prepare and submit a Special Report to the Comission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.
4.
With the MTC more negative than the limit of 3.1.1.4b l
above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With K,ff 1 1.0
'#See Special Test Exception 3.10.3 NORTH ANNA - UNIT 1 3/4 1-6 Amendment No. /d, 85
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.4 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a.
The MTC shall be measured and compared to the BOL Limit of Specification 3.1.1.4a above, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading, b.
The MTC shall be measured at any THERMAL POWER and compared to -3. 3 x 10-4 ak/k/*F (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium In the event this comparison boron concentration of 300 ppm.
indicated the KTC is more negative than -3.3 x 10'4 Ak/k/'F.
l the MTC shall be rameasured, and compared to the EOL MTC limit of specification 3.1.1.4.b. at Igt once per 14 EFPD during the renainder of the fuel cycle.
(1) Once the equilibrium boron concentration (all rods withdrawn, RATED THERMAL POWER condition) is 60 ppn or less, further measurement of the MIC in accordance with 4.1.1.4.b may be suspended providing
< 60 ppn is less negative than -4.0 x 10 gron concentration of that the measured tiTC at an equilibrium b ak/k/*F.
NORTH ANNA-UNIT 1 3/4 1-6a Amendment No. 85
L.-
i 3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity tran-sients associated with postulated accident ccnditions are controllable within acceptable limits, and 3) the reactor will be maintained suf-ficiently suberitical to preclude inadvertent criticality in the shut-down condition.
SHUTDOWN MARGIN requirements vary throughout core life as a fun-ction of fuel depletion, RCS boron concentration, and RCS Tat no 18X8. The most restrictive condition occurs at EOL, with T operating a
temperature, and is associated with a postulated Neam line break ac-cident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1.77% ak/k is initially required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requiremant is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T
<200aF, the reactivity transientsresultingfromapostulatedst$XElinebreakcooldownare minimal. A 1.77% ak/k shutdown margin provides adequate protection for the boron dilution accident.
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensums that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 9957 cubic feet in approximately 30 minutes. The reactivity change rate associated with boron reductions will therefere be within the capability for operator recognition and control.
3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC)
The limitations on MTC are provided to ensure that the value of this coefficient remains within the limiting conditions assumed for this parameter in the FSAR accident and transient analyses.
The MTC values of this specification are applicable to a' specific set of plant conditions; accordingly, verification of MTC values at NORTH ANNA - UNIT 1 B 3/4 1-1
~
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) (Continued) conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.
The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions. These corrections involved sub-tracting the incremental change in the MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED limiting MTC value -4.4 x 10 js value of the MDC was then transformed 1nto the l
THERMAL POWER conditions. Th ak/k/'F. The MTC value of -3.3 x 10 -4 ak/k/*F represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained by making these corrections to the limiting MTC value -4.4 x 10-4 ak/k/*F.
I Once the equilibriun boron concentration falls below about 60 ppm, dilution operations take an extended amount of time and reliable MTC measurements become more difficult to obtain due to the potential for fluctuating core conditions over the test interval. For this reason, MTC measurements may be suspended providedthemeasuredMTCvalueatanequjlibriumfullpowerboronconcentration
< 60 ppm is less negative than -4.0 x 10-delta k The difference between This value and the limiting MTC value of -4.4 x 10 fk/'F.
delta k/k/*F conservatively bounds the maximum credible change in MTC between the 60 ppm equilibrium boron concentration (all rods withdrawn, RATED THERMAL POWER conditions) and the licensed end-of-cycle, including the effect of rods, boron concentration, burnup, and end-of-cycle coastdown.
The surveillance requirements for measurement of the MTC at the beginning and near the end of each fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 541*F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, and 3) the P-12 interlock is above its setpoint.
3/4.1.2 BORATION SYSTEMS The boron injection sy: tem ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1) borated water sources, 2) charging pumps,
- 3) separate flow paths, 4) boric acid transfer oumps, 5) associated heat tracing systems, and 6)'an emergency power supply from t.0ERABLE diesel generators.
NORTH ANNA - UNIT I B 3/4 1-2 Amendment No. 85
o UNITED STATES
~g
[,.r..
g NUCLEAR REGULATORY COMMISSION t
-l WASHINGTON, D. C. 20555
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VIRGINIA ELECTRIC AND POWER COMPANY OLD DOVINION ELECTRIC COOPERATIVE DOCKET NO. 50-339 NORTH ANNA POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. NPF-7 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for awndment by Virginia Electric and Power Company, et al., (the licensee) dated January 3,1986, complies with the standards and require:nents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; R.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1
____,.._m.
?-
0 2.
Accordingly, the license is amended by changes to the Technical Speci-fications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-7 is hereby amended to read as follows:
(?) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9
Leste
. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: September 8, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO. 72' TO FACILITY OPERATING LICENSE NO. NPF-7 DOCKET NO. 50-339 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain docJment completeness.
Page 3/4 1-5 3/4 1-6 B3/4 1-2 l
a 0
REACTIVITY CONTROL SYSTEMS ~
MODERATOR TEMPERATURE r0 EFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
a.
For the al rods withdrawn, beginning of core life condition
<0.6 x 10' ak/k/*F below 70 percent RATED THERMAL POWER 10.0 x 10- ak/k/'F at or above 70 percent RATED THERMAL POWER.
b.
Less negative than -4.4 x 10-4 ok/k/'F for all the rods withdrawn, and of core life at RATED THERiiAL POWER.
APPLICABILITY:
Specification 3.1.1.4.a - MODES 1 and 2* only#
Specification 3.1.1.4.b - MODES 1, 2 and 3 only#
ACTION:
a.
With the MTC more positive than the limit of 3.1.1.4.a above, operations in MODES 1 and 2 may proceed provided:
1 Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than 0 delta k/k/*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6.
l 2.
The control rods are maintained within the withdrawal limits established above until subsequent measurement verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.
1 3.
Prepare and submit. a Special Report to the Comission pursuant to Specification f'A.2 within'10 days, describing the value of i
the measured MTC,1 the interim control rod withdrawal linits and the predicted ' average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn l
condition.
b.
With the ! TC more negative than the limit of 3.1.1.4.b above, be in l
HOT SHUTDOW'l within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With K,ff y,1.0
- See Special Test Exception 3.10.3 I
l NORTH AN'lA - UNIT 2 3/4 1-5 Amendment No. $7.57, 72 I
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.4 The MTC shall be determined to be within its limits during each fuel cycle as follows:
The MTC shall be measured and compared to the BOL Limit of a.
Specification 3.1.1.4.a above, prior to initial operation above 5% of RATER THERMAL POWER, after each fuel loading.
b.
The MTC shall be measured at any THERHAL POWER and compared to -3.3 x 10-4 delta k/k/*F (all rods withdrawn, RATED THERfiAL l
POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.
In the event this comparison indicated the MTC is more negative than -3.3 x 10-4 delta k/k/'F, I
the MI'C shall be remeasured, and compared to the EOL MTC limit of specification 3.1.1.4.b at legt once per 14 EFPD during the remainder of the fuel cycle.lli (1) Once the equilibrium baron concentration (all rods withdrawn, RATED THERMAL POWER condition) is 60 ppm or less, further measurement of the MTC in accordance with 4.1.1.4.b may be suspended providing that the measured MTC at an equilibriug boron concentration of <60 ppm is
~
less negative than -4.0 x 10-9 ok/k/*F.
fl0RTH ANNA - Uti!T 2 3/4 1-6 Amendment No.$1, 72
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 80 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made suberitical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
S!!UTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,y.
The most restrictive condition occurs at EOL, with T,yg at no load operat ng temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown.
In the analysis of this accident, a minimum SHUTOOWN MARGIN of 1.77% delta k/k is required to control the reactivity transient.
Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T,yg less than 200'F, the reactivity transients resulting from a postulated steem line break cooldown are minimal.
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM, as provided by either one RCP or one RHR pump as required by Specification 3.4.1.1, provides adequate mixing, pru ents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 9957 cubic feet in approximately 30 minutes.
The reactivity change rate associated with boron reductions will therefore be within the capability for operator recognition and control. The requirement that certain valves remain closed at all times except during planned boron dilution or makeup, activities provides assurance that an inadvertent boron dilution will net occur.
l NORTH ANNA - UNIT 2 8 3/4 1-1 i
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC)
The limitations on MTC are provided to ensure that the value of this coefficient remains within the limiting conditions assumed for this parameter in the FSAR accident and transient analyses.
The MTC values of this specification are applicabla to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison..
The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions. These corrections involved subtracting the incremental change in the MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL POWER conditions. Thjs value of the MDC was then transfonned into the l delta k/k/'F. The MTC value of
-3.3 x 10 jmiting MTC value -4.4 x 10-delta k/k/'F represents a conservative value (with c burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration ang is obtained by making these corrections to the limiting MTC value -4.4 x 10- delta k/k/*F.
Once the equilibrium boron concentration falls below about 60 ppm, dilution operations take an extended amount of time and reliable MTC measurements becone more difficult to obtain due to the potential for fluctuating core conditions over the test interval. For this reason, MTC measurements may be suspended provided the measured MTC value at an egyilibrium full power boron concentration
<60 ppm is less negative than -4.0 x 10-4 delta k/k/'F. The difference between This value and the limiting MTC value of 4.4 x 10-4 delta k/k/*F conservatively bounds the maximum credible change in MTC between the 60 ppm equilibrium boron concentration (all rods withdrawn RATED THERMAL POWER conditions) and the licensed end of cycle, including the effect of rods, boron concentration, burnup, and end-of-cycle coastdown.
The surveillance requirements for measurement of the MTC at the beginning and near the end of each fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 541'F. This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, and 3) the P-12 interlock is above its setpoint, 4) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and
- 5) the reactor pressure vessel is above its minimum RTNOT temperature.
NORTH ANNA - UNIT 2 B 3/4 1-2 Amendment No. 72